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ML17214A410 +
L-83-263, Summarizes 830425 Meeting W/Nrc Re Reactor Vessel Internals & Thermal Shield Plant Recovery Program Concerning Pressurized Thermal Shock.Plant May Safely Operate W/O Restriction from Pressurized Thermal Shock Considerations +, L-83-264, Forwards Plant Recovery Plan Presented at 830425 Meeting Re Reactor Vessel Internals & Thermal Shield,In Response to Item C of .Plan Will Be Revised Daily W/Updates Provided Upon Availability +, L-83-265, Forwards Reactor Vessel Internals & Thermal Shield Plant Recovery Program Per 830419 Commitment to Provide Safety Assessment of Possible Effects on Fuel Performance Due to Loose Parts.No Fuel Problems Indicated at Facility +, L-83-280, Advises That 10-yr pressure-temp Operating Limits (P-T) for Plant Recovery Program Reactor Vessel Internals & Thermal Shield Valid for Upcoming Cycle 6.P-T Limits Will Be Reviewed & Revised,If Necessary,Prior to Exceeding 7.4 EFPY +, L-83-345, Discusses Updated Submittal Dates for Reactor Vessel Internals & Thermal Shield Recovery Programs as Followup to Safety Assessment Provided at 830603 Meeting +, L-83-367, Comments on Plant Recovery Program Re Reactor Vessel Internals & Thermal Shield (Gamma Heating Effect of Removal of Thermal Shield).Gamma Heating Slight Benefit to Vessel Integrity +, L-83-452, Summarizes 830816 Meeting W/Nrc to Discuss Reactor Vessel Internals & Thermal Shield & Plant Recovery Program - Reactor Vessel Internals & Insp Results.Remaining Info Submittal Dates Listed +, L 33408 +, L-83-230, Lists Info Re Reactor Vessel Internals & Thermal Shield Plant Recovery Program to Be Provided Prior to Startup,Per 830413 Telcon.Reactor Vessel Internals & Thermal Shield Insp Results Will Be Provided Prior to Startup +, L-83-430, Confirms That Meeting to Discuss Plant Recovery Progress, Reactor Vessel Internals Insp Results & Evaluation of Core Support Barrel Visual NDE Will Be Held During Wk of 830815, Per 830726 Discussion +, L-83-369, Forwards Assessment of Safety Impacts of Removal of Thermal Shield from Facility,Per 830419 Commitment.Assessment Addresses Cycle 6 Reload Safety Analysis of Plant Recovery Program + and L-83-429, Forwards Corrected Safety Assessment as Result of Thermal Shield Removal,Submitted w/830623 Ltr +
Has query"Has query" is a predefined property that represents meta information (in form of a <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Subobject">subobject</a>) about individual queries and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
L-83-452, Summarizes 830816 Meeting W/Nrc to Discuss Reactor Vessel Internals & Thermal Shield & Plant Recovery Program - Reactor Vessel Internals & Insp Results.Remaining Info Submittal Dates Listed +, L-83-452, Summarizes 830816 Meeting W/Nrc to Discuss Reactor Vessel Internals & Thermal Shield & Plant Recovery Program - Reactor Vessel Internals & Insp Results.Remaining Info Submittal Dates Listed +, L-83-452, Summarizes 830816 Meeting W/Nrc to Discuss Reactor Vessel Internals & Thermal Shield & Plant Recovery Program - Reactor Vessel Internals & Insp Results.Remaining Info Submittal Dates Listed +, L-83-452, Summarizes 830816 Meeting W/Nrc to Discuss Reactor Vessel Internals & Thermal Shield & Plant Recovery Program - Reactor Vessel Internals & Insp Results.Remaining Info Submittal Dates Listed +, L-83-452, Summarizes 830816 Meeting W/Nrc to Discuss Reactor Vessel Internals & Thermal Shield & Plant Recovery Program - Reactor Vessel Internals & Insp Results.Remaining Info Submittal Dates Listed +, L-83-452, Summarizes 830816 Meeting W/Nrc to Discuss Reactor Vessel Internals & Thermal Shield & Plant Recovery Program - Reactor Vessel Internals & Insp Results.Remaining Info Submittal Dates Listed +, L-83-452, Summarizes 830816 Meeting W/Nrc to Discuss Reactor Vessel Internals & Thermal Shield & Plant Recovery Program - Reactor Vessel Internals & Insp Results.Remaining Info Submittal Dates Listed +, L-83-452, Summarizes 830816 Meeting W/Nrc to Discuss Reactor Vessel Internals & Thermal Shield & Plant Recovery Program - Reactor Vessel Internals & Insp Results.Remaining Info Submittal Dates Listed +, L-83-452, Summarizes 830816 Meeting W/Nrc to Discuss Reactor Vessel Internals & Thermal Shield & Plant Recovery Program - Reactor Vessel Internals & Insp Results.Remaining Info Submittal Dates Listed +, L-83-452, Summarizes 830816 Meeting W/Nrc to Discuss Reactor Vessel Internals & Thermal Shield & Plant Recovery Program - Reactor Vessel Internals & Insp Results.Remaining Info Submittal Dates Listed +, L-83-452, Summarizes 830816 Meeting W/Nrc to Discuss Reactor Vessel Internals & Thermal Shield & Plant Recovery Program - Reactor Vessel Internals & Insp Results.Remaining Info Submittal Dates Listed +, L-83-452, Summarizes 830816 Meeting W/Nrc to Discuss Reactor Vessel Internals & Thermal Shield & Plant Recovery Program - Reactor Vessel Internals & Insp Results.Remaining Info Submittal Dates Listed + and L-83-452, Summarizes 830816 Meeting W/Nrc to Discuss Reactor Vessel Internals & Thermal Shield & Plant Recovery Program - Reactor Vessel Internals & Insp Results.Remaining Info Submittal Dates Listed +
August 22, 1983 +
L-83-263, Summarizes 830425 Meeting W/Nrc Re Reactor Vessel Internals & Thermal Shield Plant Recovery Program Concerning Pressurized Thermal Shock.Plant May Safely Operate W/O Restriction from Pressurized Thermal Shock Considerations +, L-83-264, Forwards Plant Recovery Plan Presented at 830425 Meeting Re Reactor Vessel Internals & Thermal Shield,In Response to Item C of .Plan Will Be Revised Daily W/Updates Provided Upon Availability +, L-83-265, Forwards Reactor Vessel Internals & Thermal Shield Plant Recovery Program Per 830419 Commitment to Provide Safety Assessment of Possible Effects on Fuel Performance Due to Loose Parts.No Fuel Problems Indicated at Facility +, L-83-280, Advises That 10-yr pressure-temp Operating Limits (P-T) for Plant Recovery Program Reactor Vessel Internals & Thermal Shield Valid for Upcoming Cycle 6.P-T Limits Will Be Reviewed & Revised,If Necessary,Prior to Exceeding 7.4 EFPY +, L-83-345, Discusses Updated Submittal Dates for Reactor Vessel Internals & Thermal Shield Recovery Programs as Followup to Safety Assessment Provided at 830603 Meeting +, L-83-367, Comments on Plant Recovery Program Re Reactor Vessel Internals & Thermal Shield (Gamma Heating Effect of Removal of Thermal Shield).Gamma Heating Slight Benefit to Vessel Integrity +, L-83-452, Summarizes 830816 Meeting W/Nrc to Discuss Reactor Vessel Internals & Thermal Shield & Plant Recovery Program - Reactor Vessel Internals & Insp Results.Remaining Info Submittal Dates Listed +, L 33408 +, L-83-230, Lists Info Re Reactor Vessel Internals & Thermal Shield Plant Recovery Program to Be Provided Prior to Startup,Per 830413 Telcon.Reactor Vessel Internals & Thermal Shield Insp Results Will Be Provided Prior to Startup +, L-83-430, Confirms That Meeting to Discuss Plant Recovery Progress, Reactor Vessel Internals Insp Results & Evaluation of Core Support Barrel Visual NDE Will Be Held During Wk of 830815, Per 830726 Discussion +, L-83-369, Forwards Assessment of Safety Impacts of Removal of Thermal Shield from Facility,Per 830419 Commitment.Assessment Addresses Cycle 6 Reload Safety Analysis of Plant Recovery Program + and L-83-429, Forwards Corrected Safety Assessment as Result of Thermal Shield Removal,Submitted w/830623 Ltr +
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20:23:35, 8 January 2025 +
5 +
Request +
August 22, 1983 +
Washington + and Florida +
Summarizes 830816 Meeting W/Nrc to Discuss Reactor Vessel Internals & Thermal Shield & Plant Recovery Program - Reactor Vessel Internals & Insp Results.Remaining Info Submittal Dates Listed +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.